Positron Spectroscopy of Defects in Hydrogen-Saturated Zirconium

Bibliographic Details
Parent link:Defect and Diffusion Forum: Scientific Journal
Vol. 373 : Positron Annihilation - ICPA-17.— 2016.— [P. 138-141]
Corporate Authors: Национальный исследовательский Томский политехнический университет (ТПУ) Физико-технический институт (ФТИ) Кафедра общей физики (ОФ), Национальный исследовательский Томский политехнический университет (ТПУ) Энергетический институт (ЭНИН) Кафедра атомных и тепловых электростанций (АТЭС)
Other Authors: Bordulev Yu. S. Yuri Sergeevich, Li Ke, Laptev R. S. Roman Sergeevich, Kudiyarov V. N. Victor Nikolaevich, Lider A. M. Andrey Markovich
Summary:Title screen
Zirconium alloys, such as Zr-1Nb are widely used as cladding materials for nuclear fuel elements of light water reactors. Hydrogen embrittlement problem causes degradation of these parts of nuclear reactors. It is known, that hydrogen uptake causes changes in microstructure and defect structure of metals. The aim of this work is study of Zr-1Nb alloys’ defect structure after hydrogen saturation up to the concentration of 600 ppm. Saturation of hydrogen was carried out from the gas phase under high temperature and pressure. This study reveals the increase of average positron lifetime with the increase of hydrogen concentration. Value of the average positron lifetime achieves plateau when the concentration of hydrogen is about 600 ppm. Also the following effects were detected in the material after hydrogen uptake up to different concentrations: crystal lattice expansion, dislocations and vacancy-like defects formation, as well as the defect-hydrogen complexes formation.
Режим доступа: по договору с организацией-держателем ресурса
Language:English
Published: 2016
Subjects:
Online Access:http://dx.doi.org/10.4028/www.scientific.net/DDF.373.138
Format: Electronic Book Chapter
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=655810

MARC

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200 1 |a Positron Spectroscopy of Defects in Hydrogen-Saturated Zirconium  |f Yu. S. Bordulev, Li Ke, R. S. Laptev [et al.] 
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300 |a Title screen 
330 |a Zirconium alloys, such as Zr-1Nb are widely used as cladding materials for nuclear fuel elements of light water reactors. Hydrogen embrittlement problem causes degradation of these parts of nuclear reactors. It is known, that hydrogen uptake causes changes in microstructure and defect structure of metals. The aim of this work is study of Zr-1Nb alloys’ defect structure after hydrogen saturation up to the concentration of 600 ppm. Saturation of hydrogen was carried out from the gas phase under high temperature and pressure. This study reveals the increase of average positron lifetime with the increase of hydrogen concentration. Value of the average positron lifetime achieves plateau when the concentration of hydrogen is about 600 ppm. Also the following effects were detected in the material after hydrogen uptake up to different concentrations: crystal lattice expansion, dislocations and vacancy-like defects formation, as well as the defect-hydrogen complexes formation. 
333 |a Режим доступа: по договору с организацией-держателем ресурса 
461 1 |t Defect and Diffusion Forum  |o Scientific Journal 
463 1 |t Vol. 373 : Positron Annihilation - ICPA-17  |v [P. 138-141]  |o 17th International Conference, HendaCentury Resort in Wuhan, China, 20-25 September, 2015  |o [proceedings]  |d 2016 
610 1 |a электронный ресурс 
610 1 |a труды учёных ТПУ 
610 1 |a defect 
610 1 |a hydrogen embrittlement 
610 1 |a positron lifetime 
610 1 |a zirconium-hydrogen 
610 1 |a дефекты 
610 1 |a водород 
610 1 |a поглощения 
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701 0 |a Li Ke  |c physicist  |c engineer of Tomsk Polytechnic University  |f 1992-  |3 (RuTPU)RU\TPU\pers\46144  |9 22057 
701 1 |a Laptev  |b R. S.  |c physicist, specialist in the field of non-destructive testing  |c Associate Professor of Tomsk Polytechnic University, Doctor of Technical Sciences  |f 1987-  |g Roman Sergeevich  |y Tomsk  |3 (RuTPU)RU\TPU\pers\31884  |9 15956 
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